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Reprocessing Uranium Molybdenum Alloy Fuels Dissolution In Concentrated Nitric Acid
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Book Synopsis Reprocessing Uranium-molybdenum Alloy Fuels by : W. W. Schulz
Download or read book Reprocessing Uranium-molybdenum Alloy Fuels written by W. W. Schulz and published by . This book was released on 1960 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis REPROCESSING URANIUM-MOLYBDENUM ALLOY FUELS-DISSOLUTION IN CONCENTRATED NITRIC ACID. by :
Download or read book REPROCESSING URANIUM-MOLYBDENUM ALLOY FUELS-DISSOLUTION IN CONCENTRATED NITRIC ACID. written by and published by . This book was released on 1960 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Dissolution of U--3 wt.% Mo alloys in 12 to 14 M HNO3 solutions is discussed. Under these conditions 80 to 95% of the molybdenum content is precipitated as white hydrated molybdic oxide. Molybdic oxide precipitates are bulky; centrifuged volumes range from 6 to 17 vol.% for dissolver solutions 1.0 to 1.5:(M U. The precipitates retain some plutonium and uranium even after thorough washing with water and 1 M HNO3. Plutonium and uranium values in washed precipitates can be recovered by successive treatment of solid residues with caustic and nitric acid. Removal of nitric acid from uranium-molybdenum alloy dissolver solutions by boil-down procedures and by reaction with formaldehyde is discussed. Solutions obtained after removal of nitric acid constitute satisfactory low-acid Redox process feedstocks. (auth).
Book Synopsis Reprocessing Uranium-molybdenum Alloy Fuels by : W W. Schulz
Download or read book Reprocessing Uranium-molybdenum Alloy Fuels written by W W. Schulz and published by . This book was released on 1960 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Aqueous Processes for Dissolution of Uranium-molybdenum Alloy Reactor Fuel Elements by : L. M. Ferris
Download or read book Aqueous Processes for Dissolution of Uranium-molybdenum Alloy Reactor Fuel Elements written by L. M. Ferris and published by . This book was released on 1961 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Reprocessing of Low-enrichment Uranium-molybdenum Alloy Fuels by : W. W. Schulz
Download or read book Reprocessing of Low-enrichment Uranium-molybdenum Alloy Fuels written by W. W. Schulz and published by . This book was released on 1959 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis REPROCESSING OF LOW-ENRICHMENT URANIUM-MOLYBDENUM ALLOY FUELS. by :
Download or read book REPROCESSING OF LOW-ENRICHMENT URANIUM-MOLYBDENUM ALLOY FUELS. written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Procedures for the dissolution of U-Mo alloy fuels to prepare feed solutions for low-acid (Redox) type solvent extraction processing are presented. U-Mo alloys can be dissolved in boiling ferric nitrate--ritric acid solutions to higher terminal urarium concentrations and lower terminal acidities without precipitation of uranyl molybdate than in nitric acid alone. Anion resin exchange studies indicate the presence of negatively charged iron-molybdenum complex ions in the solutions. The U-Mo alloys also dissolve more rapidly in ferric nitrate--nitnic acid solutions than in nitric acid alone; dissolution rate data are given. Curves delineating free acid, uranium, snd iron (III) concentrations within which solutions stable towards solids formation can be prepared from U-3 wt.% Mo and U-10 wt.% Mo alloys are presented. Stability during prolonged storage of uranium--molybdenum-ferric nitrate--nitric acid solutions is discussed. Data on the oxidation of plutonium in these solutions and on further neutralization of the solutions are presented. Fission product decontamination and product recovery obtained in solvent extraction studies simulating the Redox process are discussed. (auth).
Book Synopsis Reprocessing of Power Reactor Fuels by :
Download or read book Reprocessing of Power Reactor Fuels written by and published by . This book was released on 1960 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis AQUEOUS PROCESSES FOR DISSOLUTION OF URANIUM-MOLYBDENUM ALLOY REACTOR FUEL ELEMENTS. by :
Download or read book AQUEOUS PROCESSES FOR DISSOLUTION OF URANIUM-MOLYBDENUM ALLOY REACTOR FUEL ELEMENTS. written by and published by . This book was released on 1961 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Methods for dissolving unirradiated uranium-molybdenum alloy reactcr fuels in nitric acid, nitric acid--ferric nitrate, and nitric acid-- phosphoric acid solutions were studied on a laboratory scale. Flowsheets based on the results propose dissolution of alloys containing 3% molybdenum in boiling 6 M HNO/ sub 3/ to yield stsble solutions that are 0.6 M in uranium and 3 to 4 M in nitric acid. The uranium can then be easily decontaminated and recovered in a conventional Purex-type tributyl phosphate solvent extraction process. Alloys containing 10% molybdenum would be dissolved in boiling 11 M HNO3, allowing molybdic oxide to precipitate. The molybdic oxide, which carries 5-10% of the uranium, is removed by centrifugation and the acidity of the supernatant solution adjusted tc allow recovery of the uranium by Purex-type solvent extraction procedures. The uranium carried by the molybdic oxide is recovered after the MoO/ sub 3/ is dissolved in warm 5 M NaOH. Less than 0.1% of the uranium is solubilized during the caustic dissolution. Alternative methods investigated involve dissolution in nitric acid containing 0.5 to 1 M ferric nitrate to complex the molybdenum. These techniques lead to undesirably large volumes of high-level solvent extraction waste solutions. Phosphate ion is also effective in complexing molybdenum; however, its use in the dissolvent would be purposeless since it must be complexed with iron during solvent extraction. Rates of reaction of the various alloys and the solubility of molybdic oxide were determined in nitric acid, nitric acid-- ferric nitrate, and nitric acid-- phosphonic acid solutions. (auth).
Book Synopsis Reprocessing of Irradiated Fission Reactor Fuel and Breeding Materials by :
Download or read book Reprocessing of Irradiated Fission Reactor Fuel and Breeding Materials written by and published by . This book was released on 1964 with total page 212 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Electrolytic Dissolution of Power Reactor Fuels in Nitric Acid by :
Download or read book Electrolytic Dissolution of Power Reactor Fuels in Nitric Acid written by and published by . This book was released on 1961 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Undissolved Uranium Aluminide in Reprocessing of Test Reactor Ruels by : B. E. Paige
Download or read book Undissolved Uranium Aluminide in Reprocessing of Test Reactor Ruels written by B. E. Paige and published by . This book was released on 1970 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Dissolution of Power Reactor Fuel Cores by : H. T. Blaine
Download or read book Dissolution of Power Reactor Fuel Cores written by H. T. Blaine and published by . This book was released on 1960 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis ELECTROLYTIC DISSOLUTION OF POWER REACTOR FUELS IN NITRIC ACID. by :
Download or read book ELECTROLYTIC DISSOLUTION OF POWER REACTOR FUELS IN NITRIC ACID. written by and published by . This book was released on 1961 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The electrolytic oxidation in nitric acid of stainless steel, zirconium, Zircaloy-2, zirconium- uranium alloy, aluminum, and uranium - molybdenum alloy was demonstrated on a laboratory scale. The rate of chemical dissolution of UO/ sub 2/ in nitric acid was measured. Corrosion of stainless steel by these dissolver solutions was measured and found to be negligible. Electrolytic dissolution was demonstrated to be a practical technique for the first step in processing fuel elements of several types of power reactors. (auth).
Book Synopsis An Analysis of Power Reactor Fuel Reprocessing by : F. L. Culler (Jr.)
Download or read book An Analysis of Power Reactor Fuel Reprocessing written by F. L. Culler (Jr.) and published by . This book was released on 1957 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Reprocessing of Power Reactor Fuels by :
Download or read book Reprocessing of Power Reactor Fuels written by and published by . This book was released on 1958 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Reprocessing of Irradiated Fission Reactor Fuel and Breeding Materials by :
Download or read book Reprocessing of Irradiated Fission Reactor Fuel and Breeding Materials written by and published by . This book was released on 1958 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Reprocessing of Uranium-molybdenum Alloy Reactor Fuels by : Wallace W. Schulz
Download or read book Reprocessing of Uranium-molybdenum Alloy Reactor Fuels written by Wallace W. Schulz and published by . This book was released on 1960 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: